Erosion and deuterium retention investigation of mixed W-Be layer on Be in experiments on plasma disruption simulation

被引:0
|
作者
Korshunov, SN [1 ]
Vasiliev, VI [1 ]
Guseva, MI [1 ]
Gureev, VM [1 ]
Danelyan, LS [1 ]
Zatekin, VV [1 ]
Kulikauskas, VS [1 ]
机构
[1] Russian Res Ctr, Kurchatov Inst, Moscow 123182, Russia
关键词
D O I
暂无
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The mixed W-Be layers were prepared by depositing of Be and W atoms on Be substrate under simultaneous sputtering of Be and W targets by 20 keV Ar+-ions. The thickness of the deposited mixed W-Be layer was similar to 500 nm. The element composition analysis of these layers showed that mixed layer contains up to 35 at.% W, up to 35 at.% Be and up to 30 at.% O. The W-Be films on Be were irradiated by pulsed deuterium plasma flux in the electrodynamic plasma MKT-accelerator at the deuterium plasma concentration of 10(21) m(-3), maximal ion energy of (1-2) keV and with the energy flux density of 0.2 MJ/m(2) per pulse. The pulse duration was equal to 60 mus. After irradiation by two plasma pulses the W-Be film is melted and removed completely from the local surface areas. The element distributions in a mixed layer after an effect of the pulsed plasma ate essentially changed. For the surface areas with the removed film the Be concentration is about 75 at.%, W - about 15 at.%, O - about 10 at.% and the penetration of W and O atones up to 1000 nm in depth of Be substrate is observed. For the surface areas with the retained melted film the Be surface concentration increase up to 90 at.%, tungsten and oxygen concentration decrease about 2-3 times. The method of Elastic Recoil Detection Analysis was used to study D retention. The integral deuterium concentrations ate equal to 0.6 10(20) and 2.2 10(20) m(-2) tot the removed him areas and for the retained melted film ones, correspondingly. Consequently, deposited W-Be film promotes the essential reduction of D retention in Be substrate. Transmission electron microscopy was used to study the erosion product size distribution. The erosion products were collected an basalt filter fibers located in a shadow of the pulsed plasma flux around the exposed W-Be film target. The erosion product size distribution has two maxima located in the ranges 0.1-0.2 mum and 2.5-5.0 mum.
引用
收藏
页码:285 / 290
页数:6
相关论文
共 50 条
  • [1] Erosion and deuterium retention investigation of mixed W-Be layers on Be in experiments on plasma disruption simulation
    Korshunov, SN
    Vasiliev, VI
    Guseva, MI
    Gureev, VM
    Danelyan, LS
    Zatekin, VV
    Kulikauskas, VS
    FUSION TECHNOLOGY, 2000, 38 (03): : 357 - 362
  • [2] The investigation of mixed W-C and W-Be layer after irradiation by pulsed deuterium plasma flux
    Guseva, M.I.
    Danelyan, L.S.
    Zatekin, V.V.
    Kulikauskas, V.S.
    Shvej, I.V.
    Poverkhnost Rentgenovskie Sinkhronnye i Nejtronnye Issledovaniya, 2001, (05): : 62 - 66
  • [3] Investigation of fusion reactor candidate materials erosion in plasma disruption simulation experiments
    Yakushin, VL
    Kalin, BA
    Shul'ga, AV
    Fedotov, VT
    Plyuschev, AN
    JOURNAL OF NUCLEAR MATERIALS, 1998, 258 : 1127 - 1132
  • [4] Investigation of fusion reactor candidate materials erosion in plasma disruption simulation experiments
    Yakushin, V.L.
    Kalin, B.A.
    Shul'ga, A.V.
    Fedotov, V.T.
    Plyuschev, A.N.
    Journal of Nuclear Materials, 1998, 258-263 (pt A): : 1127 - 1132
  • [5] Deuterium retention in deposited W layer exposed to EAST deuterium plasma
    Katayama, K.
    Ashikawa, N.
    Ding, F.
    Mao, H.
    Zhou, H. S.
    Luo, G. N.
    Wu, J.
    Noguchi, M.
    Fukada, S.
    NUCLEAR MATERIALS AND ENERGY, 2017, 12 : 617 - 621
  • [6] Plasma shield dynamics and target erosion in disruption simulation experiments
    Würz, H
    Pestchanyi, S
    Kappler, F
    FUSION ENGINEERING AND DESIGN, 2000, 49-50 : 389 - 395
  • [7] Influence of plasma pressure gradient on melt layer macroscopic erosion of metal targets in disruption simulation experiments
    Tereshin, VI
    Garkusha, IE
    Bandura, AN
    Byrka, OV
    Chebotarev, VV
    Makhlaj, VA
    Solyakov, DG
    Wuerz, H
    JOURNAL OF NUCLEAR MATERIALS, 2003, 313 : 685 - 689
  • [8] Modeling and simulation of melt-layer erosion during a plasma disruption
    Hassanein, A
    Belan, V
    Konkashbaev, I
    Nikandrov, L
    Safronov, V
    Zhitlukhin, A
    Litunovsky, V
    JOURNAL OF NUCLEAR MATERIALS, 1997, 241 : 288 - 293
  • [9] Erosion and deuterium retention of CLF-1 steel exposed to deuterium plasma
    Qiao, L.
    Wang, P.
    Hu, M.
    Gao, L.
    Jacob, W.
    Fu, E. G.
    Luo, G. N.
    PHYSICA SCRIPTA, 2017, T170
  • [10] Investigation of vanadium alloys in CTR plasma disruption-simulation experiments
    Yakushin, VL
    Kalin, BA
    Kraskovskaya, NV
    Votinov, SN
    Vasiliev, VI
    JOURNAL OF NUCLEAR MATERIALS, 1996, 233 : 390 - 394